22.313 Thermal Hydraulics in Nuclear Power Technology, Spring 2003

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Author(s)
Todreas, Neil E.
Alternative Title
Thermal Hydraulics in Nuclear Power Technology
Date Issued
June 2003
Abstract
Advanced topics emphasizing thermo-fluid dynamic phenomena and analysis methods. Single-heated channel-transient analysis. Multiple-heated channels connected at plena. Loop analysis including single and two-phase natural circulation. Kinematics and dynamics of two-phase flows with energy addition. Boiling, instabilities, and critical conditions. Subchannel analysis.
Subjects
thermo-fluid dynamic phenomena
Single-heated channel-transient analysis
Multiple-heated channels
Loop analysis
single and two-phase natural circulation
Kinematics
two-phase flows
Subchannel analysis. Core thermal analysis
Hydraulics
Nuclear energy
MIT Department
Massachusetts Institute of Technology. Department of Nuclear Science and Engineering
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